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Intercomparison of results for a PWR rod ejection accident

Intercomparison of results for a PWR rod ejection accident D.J. Diamond a, A. Aronson a, J. Jo a, A. Avvakumov b, V. Malofeev b, V. Sidorov b, P. Ferraresi c, C. Gouin c, S. Aniel d, M.E. Royer d a Brookhaen National Laboratory, Nuclear Energy and Infrastructure Systems Diison, Energy Sciences and Technology Department, Building 130, P.O. Box 5000, Upton, NY 11973- 5000, USA b Russian Research Centre-Kurchato Institute, Moscow, Russia c Institute for Protection and Nuclear Safety, Cadarache, France d Atomic Energy Commission (CEA ), Saclay, France

Document type > *Congrès/colloque

Keywords > computer code, nuclear fuel

Research Unit > DRS (Security research department)

Authors > [et al.]

Publication Date >  


This study is part of an overall program to understand the uncertainty in best-estimate calculations of the local fuel enthalpy during the rod ejection accident. Local fuel enthalpy is used as the acceptance criterion for this design-basis event and can also be used to estimate fuel damage for the purpose of determining radiological consequences. The study used results from neutron kinetics models in PARCS, BARS, and CRONOS2, codes developed in the United States, the Russian Federation, and France, respectively. Since BARS uses a heterogeneous representation of the fuel assembly as opposed to the homogeneous representations in PARCS and CRONOS, the effect of the intercomparison was primarily to compare different intra-assembly models. Quantitative comparisons for core power, reactivity, assembly fuel enthalpy and pin power were carried out. In general, the agreement between methods was very good, providing additional confidence in the codes and providing a starting point for a quantitative assessment of the uncertainty in calculated fuel enthalpy using best-estimate methods. © 2001 Elsevier Science B.V. All rights reserved.
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